Title :
Improved geometrical design of the US DCLL ITER test blanket module
Author :
Marriott, E. ; Sawan, M. ; Dagher, M. ; Wong, C.
Author_Institution :
Fusion Technol. Inst., Univ. of Wisconsin-Madison, Madison, WI, USA
Abstract :
Computational fluid dynamics simulations have demonstrated flow problems within the helium flow path in the current US DCLL ITER test blanket module design. New geometry for the helium flow path has been designed that will improve flow evenness and simplify the overall helium flow path within the test blanket module while maintaining the overall test blanket module geometry. Global changes to the test blanket module geometry can be implemented based on these improvements.
Keywords :
Tokamak devices; computational fluid dynamics; fusion reactor blankets; fusion reactor design; US DCLL ITER test blanket module; computational fluid dynamics; flow problem; geometrical design; helium flow path; Assembly; Heating; Helium; CFD; ITER; blanket; test blanket module;
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
DOI :
10.1109/SOFE.2011.6052310
